Optimization of RW volumes from reprocessing of SNF from fast reactors. Fractionation options
| Autor: | S A Dmitriev, V. A. Kascheev, A Yu Shadrin |
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| Rok vydání: | 2020 |
| Předmět: | |
| Zdroj: | Journal of Physics: Conference Series. 1475:012023 |
| ISSN: | 1742-6596 1742-6588 |
| Popis: | In this work, are analyzed the volume of vitrified radioactive waste generated during the processing of spent nuclear fuel from fast reactors (using the example of processing mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor). The analysis showed - there is a minimum acceptable volume of HLW from spent nuclear fuel reprocessing, determined by the parameters of permissible thermal and radiation effects on the matrices used for RW utilization, as well as by the restriction on the chemical composition of the matrices, fixed in regulatory documents; - the allocation of the fraction of minor actinides (MA) during the reprocessing of the fast reactor spent nuclear fuel significantly reduces the required volume of the matrix for disposal of HLW; - the currently technically achievable level of MA (99.9%) and plutonium (99.975%) recovery during the reprocessing SNF allows reducing the time to achieve radiation equivalence of the generated RW and uranium feed used to produce mixed nitride uranium-plutonium nuclear fuel to 300 years; - a complete rejection of the deep underground disposal of RW from SNF reprocessing (rejection of the formation of radioactive waste of the 1st and 2nd classes) is not economically justified, because leads to the need for the formation of a large volume of RW of the 3rd class; - minimization of the RW volume to be deep disposed is achieved by a combination of fractionation (separation of the MA fraction) and the use of the principle of multi-stage processing of HLW, which assumes long-term intermediate controlled storage of HLW (50-60 years). |
| Databáze: | OpenAIRE |
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